-->

학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) A Measurement of the Break Flow Rates in the ATLAS Hyun-Sik Park, Ki-Yong Choi, Seok Cho, Kyoung-Ho Kang, Nam-Hyun Choi, Dae-Hun Kim, Byong-Jo Yun, and PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Thermal-hydraulic Characteristics in the Reactor Coolant System of the ATLAS During LBLOCA Test of LB-CL-15 D. H. Kim, H. S. Park, K. Y. Choi, S. Cho, K. H. Kang, Y. S. Kim, N. H. Choi, K. H. Min, and B. D. K PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Conceptual Design Study of the RCP Test Loop Won-Myung Choung, Chang-Hwan Chung, Heung-June Chung, Jin-Seok Park, Ji-Won Yeo, Tae-Soon Kwon, Chan PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Basic Study for Active Nucleation Site Density Evaluation in Subcooled Flow Boiling In-Cheol Chu and Chul-Hwa Song (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Analysis of a CHF Disappearing Phenomenon and the Prediction Correlations for the Threshold Pressures S. D. Hong and W. J. Lee (KAERI), G. C. Park (SNU) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development of a CANDU Fuel Channel Model to Assess the Effect of a Pressure Tube Creep on the Safety Related Paramters Under a Stratified Two-Phase Flow Bo Wook Rhee, Gyu-Hong Roh, Hyung Tae Kim, and Joo Hwan Park (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development of a Wrapper Object, TRelap, for RELAP5 Code for Use in Object Oriented Programs Young Jin Lee (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Preliminary CFD Analysis on Debris Transport to ECCS Sump in Recirculation Mode for Kori Unit 3 Su Won LEE, Kyung Jin LEE, and Soon Joon HONG (FNC), Sung Bok LEE and Hyeong Taek KIM (KHNP) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Multi-dimensional Analysis for Upper Plenum Injection Using MARS-KS Code Kyung Won Lee, Yong Jin Cho, and Seung Hoon Ahn (KINS) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) The Effect of TBS LOCA on the SIS Design for OPR1000 Byung Heon Hwang, Cheol Woo Kim, and Eun Kee Kim (KOPEC) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Temperature Distribution Analysis for Monitoring Sample in Reactor Using FEM and FDM Method Chang-Keun Yang and Yohan Kim (KEPRI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development of a Mesh Handling System for the SPACE Pilot Code Je. Woo. Cho, C. E. Park, and S. Y. Lee (KOPEC) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) A Comparative Analysis for Control Rod Drop Accident in WH and CE Type Chang-Keun Yang, Yo-Han Kim, and Jun-Sang Ha (KEPRI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Steady-State Calculation of RD-14M Small Break LOCA Experiments by CATHENA Code Hyoung Tae Kim, Joo Hwan Park, and Sang Baik Kim (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) The Validation Region of the Boussinesq Approximation for Nuclear Reactor Operation and Atmospheric Pressure Conditions Hyuk kwon, K. W. Seo, and D. H. Hwang (KAERI) PDF보기 -
Last Modified : 1998-Autumn